ML18262A077

July 10, 2018, Summary of the Category 1, Public Teleconference to Discuss Nuscale Power Llls Request for Additional Information Responses 8843, 9201, 9213, 9188, and 9436

ML18262A077
Person / Time
Site:	NuScale
Issue date:	09/24/2018
From:	Bavol B NRC/NRO/DLSE/LB1
To:	Samson Lee NRC/NRO/DLSE/LB1
Bavol B / NRO/ 415-6715
References
Download: ML18262A077 (5)

Text

September 24, 2018 MEMORANDUM TO:

Samuel S. Lee, Chief Licensing Branch 1 Division of Licensing, Siting, and Environmental Analysis Office of New Reactors FROM:

Bruce M. Bavol, Project Manager

/RA/

Licensing Branch 1 Division of Licensing, Siting, and Environmental Analysis Office of New Reactors

SUMMARY

OF THE JULY 10, 2018, CATEGORY 1, PUBLIC TELECONFERENCE TO DISCUSS NUSCALE POWER LLCS RESPONSES TO REQUEST FOR ADDITIONAL INFORMATION NOS. 8843, 9201, 9213, 9188, AND 9436 The U.S. Nuclear Regulatory Commission (NRC) held a Category 1 public teleconference on July 10, 2018, to discuss the NuScale Power, LLC (NuScale) request for additional information responses pertaining to leak before break and reactor vessel materials. Participants included personnel from NuScale. No members of the general public participated via bridgeline during the meeting.

The public meeting notice dated June 27, 2018, can be found in the NRCs Agencywide Documents Access and Management Systems under Accession No. ML18178A439. This meeting notice was also posted on the NRC public website.

Enclosed is the meeting agenda (Enclosure 1), list of participants (Enclosures 2), and overview (Enclosure 3).

Docket No.52-048

Enclosures:

1. Meeting Agenda

2. List of Attendees

3. Meeting Overview cc w/encl.: DC NuScale Power, LLC Listserv CONTACT: Bruce M. Bavol, NRO/DLSE 301-415-6715

ML18262A077

• By email NRO-002 OFFICE DLSE/LB1:PM DLSE/LB1:LA DEIA/MCB DLSE/LB1:PM NAME BBavol MMoore MMitchell BBavol (signed)

DATE 9/19/2018 9/19/2018 9/20/2018 9/24/2018

U.S. NUCLEAR REGULATORY COMMISSION CATEGORY 1 PUBLIC TELECONFERENCE TO DISCUSS NUSCALE POWER, LLCS REQUEST FOR ADDITIONAL INFORMATION RESPONSES -

LEAK-BEFORE-BREAK TECHNICAL SPECIFICATIONS AND (RAI NOS. 9188, 9436)

REACTOR VESSEL MATERIALS MEETING AGENDA July 10, 2018 The purpose of this teleconference was for the U.S. Nuclear Regulatory Commission (NRC) staff to discuss technical issues that need to be resolved associated with the NuScale Power, LLC (NuScale) Design Certification Application review in progress.

First Part of Meeting - Leak-Before-Break (LBB)/ Technical Specifications (TS) (Request for Additional Information (RAI) No. 8843, RAI No. 9201, and RAI No. 9213)

Second Part of Meeting - Chapter 5, Reactor Vessel Materials (RAI No. 9188, RAI No. 9436)

Time Topic Speaker 1:00-1:05 Introductions and identification of topics NRC 1:05-2:30 RAI discussions (LBB/TS)

NRC/NuScale 2:30-2:45 Questions from the public Public 2:45-3:30 Break 3:30-4:15 RAI discussions (Ch5 - 9188, 9436)

NRC/NuScale 4:15-4:30 Questions from the public Public

U.S. NUCLEAR REGULATORY COMMISSION CATEGORY 1 PUBLIC TELECONFERENCE TO DISCUSS NUSCALE POWER LLCS DESIGN CERTIFICATION APPLICATION LIST OF ATTENDEES July 10, 2018 Name Organization Bruce Bavol U.S. Nuclear Regulatory Commission (NRC)

Theodore Tjader NRC Chang Li NRC Samuel Lee NRC Matthew Mitchell NRC Victor Cusumano NRC Nicholas McMurray NRC Carrie Fosaaen NuScale Power, LLC (NuScale)

Ross Snuggerud NuScale Sarah Bristol NuScale Heqin Xu NuScale Pei-Yuan Cheng NuScale Karl Gross NuScale John Fields NuScale Gary Becker NuScale

U.S. NUCLEAR REGULATORY COMMISSION CATEGORY 1 PUBLIC TELECONFERENCE TO DISCUSS NUSCALE POWER LLCS REQUEST FOR ADDITIONAL INFORMATION RESPONSES The purpose for this meeting was to inform NuScale Power, LLC (NuScale) of initial U.S.

Nuclear Regulatory Commission (NRC) review findings on the issue of leak-before-break (LBB) application and to look for the path of resolution. NuScale design applies leak-before-break (LBB) to main steam (MSS) and feedwater (FWS) pipe breaks without limiting condition for operation (LCO) for the LBB leakage limit. The NRC staff feels that it introduces the safety concern of a potential violation of General Design Criteria (GDC) 4 without a satisfactory justification. This concern was identified in Request for Additional Information (RAI) No. 8843, RAI No. 9201 and RAI No. 9213.

First Part of Meeting LBB/Technical Specifications (RAI Nos. 8843, RAI 9201, and RAI 9213)

NuScale responded that the MSS/FWS LBB leakage limit LCO is not needed, based on its determination that the limit does not meet the criteria in Title 10 of the Code of Federal Regulations (CFR), Section 50.36(c)(2). The NRC staff disagrees with NuScale on its no LCO determination based on NuScales interpretation of the referenced NRC documents. In addition, the NRC staff believes that 10 CFR 50.36(c)(2) Criteria 2 is met and a LCO must be established.

The LBB discussion concluded with no foreseeable path to resolution. Staff will seek guidance from NRC management on the results of this discussion with NuScale.

Second Part of Meeting Chapter 5 - Reactor Vessel Materials (RAI Nos. 9188 and 9436)

Regarding the NRC staff discussions with NuScale on responses to RAI Nos. 9188 and 9436.

NuScale agreed to provide a supplement to incorporate the information related to the lock plates and threaded inserts into the design control document. Once verified these RAIs can be resolved / closed.